ML061450397

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Browns Ferry, Unit 1, 0000-0043-8325-SRLR, Revision 1, Supplemental Reload Licensing Report for Brown Ferry 1, Reload 6 Cycle 7, Pages 123 Through End
ML061450397
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 05/15/2006
From:
Global Nuclear Fuel
To:
Office of Nuclear Reactor Regulation
References
0000-0043-8325-SRLR, Rev 1
Download: ML061450397 (72)
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Text

BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I I %125.0 --Dome Press Rise (psi)x Saet Mhle Flow"sRle V a~o lw-Bypass V\he Ravv CA-A 1.0 X0 75.0 42 25.0 lay -Yt** )(^¢ )th is' l< @0.0 5.0 10.0 Twa (sec)15.0 20.0 0.0 5.0 10.0 mum (sec)15.0 20.0 150.0 4)50.4)0 M 0 4)0.0 5.0 10.0 15.0 20.0 0.0 5.0 10.0 Time (sec) Tim (sec)15.0 20.0 Figure 62 Plant Response to FW Controller Failure (MOC ICF with TBVOOS (HBB))cc 1 Page 123 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0 150.0 A 100.0 50.0 I a 125.0.0 75.0 25.0-25.0 a Dome Press Rise (psi)Safetyh FIoN 1-a Relief Valve RFaw s Bypass Vahe Flow\1 ICIFN(% FM r 0.0 10.0 20.0 Trn (sec)0.0 10.0 Timr (sec)20.0 , 100.0 s.oI 50.0 0.0'9 4, a C6 C~0.0 100 TRm (sec)20.0 0.0 10.0 20.0 Tmu (sec)Figure 63 Plant Response to Inadvertent HPCI /L8 (MOC ICF with TBVOOS (HBR))Page 124 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 0.0 5.0 10.0 Tme (sec)150.0.x: 100.0 i*O 50.0 0.0 25.0-25.0 15.0 20.0 0.0 5.0 10.0 Tun (sec)PRT) a VWd Reactivity

-Doppler Reacvit 1.0 Scram Reactivty.0 Total Reacti 0.0.0 04 -1.0-2.0 15.0 20.0 0.0 &o 10.0 Time (sec)15.0 20.0 0.0 5.0 10.0 Time (sec)15.0 20.0 Figure 64 Plant Response to FW Controller Failure (EOC ICF with TBVOOS (HBB))Page 125 BROWNS FERRY I D Pl,.A ^0000-0043-8325-SRLR Revisinn I 200.0 I l 125.0 150.0 100.0 2 92 75.0 1 a Dome Press Rise (psi)Safety VaWe Flow-Relief Vave Flow Bypass \Mhe Flow e HPCI FlRov (% FV)25.0 50.0-25.0 l 0.0 10.0 20.0 0.0 10.0 20.0 rum (sec)Tmr (Se)10 100.0 A 6 a': '9 to 0~0.0 10.0 20.0 TRe (sec)0.0 10.0 20.0 Tint (sec)Figure 65 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS (HBB))Page 126

-BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I o.0 5.0 10.0 15.0 20.0 0.0 5.0 10.0 Tim (sec) Tune (sec)15.0 20.0 0.0 a 15.0 200 0.0 50 10.0 Tine (Sec)0.0 0.0 5.0 10.0 Trae (Sec)15.0 20.0 Figure 66 Plant Response to FW Controller Failure (MOC MELLLA with TBVOOS (HBB))CPg1 Page 127 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0 150.0 A 100.0 50.0 a NeutronFlux/10

-Ave Surface Heat Flux-Core Inlt Raw o Core Inlet Subcooling

00 10.0 Tm (See)20.0 0.0 10.0 20.0 Tine (sec)150.0 1 la 10D.0 EO.O 50.0 0.0 a Le\A(inch-REF-SEP-SKRT)

\*-Vssel Steam Flow-- Turbine Stean Flaw_ Feedwater Flaw Wo a a 0 a 2:E 0 I ffl-2.0 1 0.0 10.0 20.0 0.0 10.0 Tm (sec)20.0 Time (sec)Figure 67 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA with TBVOOS (HBB)1 )CPgCp 12 Page 128 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I A100.0 0.0 5.0 10.0 15.0 20.0 0.0 5.0 10.0 Tint (sec) Trmr (sec)15.0 20.0 la 100.0 cO O _ _ _ _ _0 Q" -1.0 "*-2.0 15.0 20.0 0.0 5.0 10.0 TumE (sec)0.0 5.0 10.0 Tkr (see)15.0 20.0 Figure 68 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS (HBB))Conr-l Page 129 BROWS FERY I00Q0-0043-8325-SRLP-BReOWNS 6 R Reload 6Revisio-n 10 10.0 0.0 Trat (IC)0.0 20.0 10.0 0.0 Tni (SCC)Figure 69 Plant Response to Inadvertent HPCI 1L8 ( EOC MELLLA with TBVOOS (LBB) )Page 130 BROWNS FERRY I-A 0000-0043-8325-SRLR Rixviinn 1 lxcl"Ua v -\ I ...... .200.0 50.A100.0 -0.0 150.0 50.0 0.0 _0.0 5.0 10.0 Tivn (sec)X 75.0 25.0-25.0 15.0 20.0 0.0 5.0 10.0 rmie (sec)RT) a Void Reactivity

-*- Doppler Reatvt 1.0 -'- ScramRatvt Topp t Reacvi 0 0.0 **-10-2.0 15.0 20.0 0.0 5.0 10.0 Tr (sc)15.0 200 5.0 10.0 Tine (sec)15.0 20.0 Figure 70 Plant Response to FW Controller Failure (EOC ICF with TBVOOS (UB))Page 131 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0 150.0 4a A 100.0-Neutron FIux/ 10 x Ave Surface Heat Flux e- Core Inlet Flow* Core Inlet Subcooling 4J 50.0 p on I -. I 0.0 10.0 20.0 0.0 10.0 20.0 Tine (sec)Tnrm (sec)1 10.00 40 so-o a a 0 a.2 C U'9I 0.0 o-0.0 10.0 20.0 0.0 10.0 20.0 Tme (sec) rmr (sec)Figure 71 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS (UB))( 71 1 Page 132 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0.0 ,, 7u 250-25.0 15.0 20.0 0.0 5.0 100.Time (sec)0.0 .00 5.0 10.0 Time (sec)150.0 100.50.0 -4..a 0 0 45 S.150 20.0 0 1 s.0 20.0 0.0 5.0 10.0 15.0 20.0 0.0 5.0 10.0 RTae (sec) Time (sec)Figure 72 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS (UB))CP \Page 133 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I I l 125.0 t.0 75.0 25.0-25.0 a Dome Press Rise (psi)-(-Safety \he low-i Relief VaI'e Flowv_ Bypass Vahoe Faw e HPCI Faw (% FW 0.0 10.0 20.0 Tim (sec)0.0 10.0 Thie (sec)20.0 qj E I.I 04 0.0 10.0 20.0 Trh (Sec)0.0 10.0 20.0 T-re (sec)Figure 73 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS (UB))C 7 1-L Page 134 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 10 it A.1"I 0.0 5.0 10.0 15.0 Tmr (see)0.0 5.0 10.0 15.0 rm (sec)'I X+150.0 ,: 10D.0 50.0 1.0 4)o- 0.0 0 U 04-1.0-2.0 Void Reactivity Doppler Reactivit Scram Reactivity Total Reactiv]ty) B.. 1 I I l 1 1 0.0 5.0 10.0 15.0 Tun (sec)0.0 5.0 10.0 Trm (sec)150 Figure 74 Plant Response to FW Controller Failure (MOC ICF & FWTR with TBVOOS (HBB))Page 135 BROWNS FERRY I n-1-A~n 4 0000-0043-8325-SRLR a.c-nn 1 1XVIVau V .11V.0xmii i 200.0 150.0 I O Neutron Flux/10-- Ave Surface Fleat Flux-& Core Inlet Flaw_ Core Inlet Subcooling A et -i -)A 100.0 4.50.0 i n oi o o o o o u.u I -_0.0 10.0 Tim (sec)20.0 0.0 10.0 20.0 Tfie (sec)150.0 a Void Reactivity

-Doppler Readivity 1.0 IScram Reactiity_ Total Reactivity 0.0 .0 V 10 100.0 s.o 50.0 t 4.04 -1 .o 0.0 10.0 Tinm (see)20.0 0.0 10.0 20.0 rm (see)Figure 75 Plant Response to Inadvertent HPCI /L8 (MOC ICF & FWTR with TBVOOS (HBB)1)C +1L Page 136:I:

BROWNS FERRY I V.-.A fu 0000-0043-8325-SRLR Qpvicinn 1-.0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 rhm (sec) Time (sec)150.0 ,: 100.0 ao a a 0 a.0 0.0 5.0 10.0 15.0 0.0 5.0 1OjO 15.0-rm (see) Time (see)Figure 76 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS (HBB))Page 137 I BROWNS FERRY I Reload 6 0000-0043-8325-SRLR D-A-C-n I L%.~Vxa..IVL I 125.0 1 e0.0 75.0 a DomTe Press Rise (psi)-* Safety Vahe Flow Relief Wmh Flow+-* Bypass Vale Flow+ HPCI Rlaw (% FW\/ o v ev .v.............

+n 25.0 I-2.U V I 0.0 10.0 20.0 Time (sec)0.0 10.0 Tune (sec)20.0 150.0 10 100.0 50.0 yt 0 a c a c S 0 U:'.0.0 0.0 10.0 rm (8CC)20.0 0.0 10.0 20.0 Tm(sc Figure 77 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS (HBB)1 )C-1 C Page 138 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 10 A so 0.0 5.0 10.0 150 Time (sec)0.0 50 10.0 15.0 TinT (sec)150.0 1.01-Void Reactivity

-Doppler Reactdlile, Scran Reactivity

+ Total Reactivity wo 1. -50.0 g o.o A -1.0-2.0 0.0 5.0 10.0 15.0 Time (sec)0.0 5.0 10.0 Tine (sec)15.0 Figure 78 Plant Response to FW Controller Failure (MOC MELLLA & FWTR with TBVOOS (HBB))cr1 Page 139 BROWNS FERRY I D.IlnnAl A 0000-0043-8325-SRLR PvAQcnn 1-.200.0 150.0 40 A 100.0 50.0 I a Ne~ FlulcK10 \otAve Surface Heat Flux I 6COrE Inlet Flow+CorelInlet Subcooling Wfi==* --125.0.0 75.0 42 25.0 n. -r r n i 0 °l UQU ! i g-25.0 o.o 150.0 l 100.0 50.0 0.0 _10.0 Turr (sec)20.0 0.0 10.0 20.0-rm (see)2 0 U U: 0.0 10.0 20.0 Tm (sem)0.0 10.0 20.0 Tme (sec)Figure 79 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA & FWTR with TBVOOS (HBB))CA%Page 140 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 4J y100.0 la 0.0 50 10.0 150 TinM (sec)0.0 5. 10.0 15.0 Tm (sec)150.0 la 100.0 50.0 Z)0 t 0 45 Q Y.0.0 5.0 10.0 15.0 Tinx (seM)0.0 5.0 100 15.0 Time (se)Figure 80 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS (HBB))c73 Page 141 BROWNS FERRY I D-ln-A A 0000-0043-8325-SRLR PpiciArrn 1 I\;lx~lmu m l\. lt S I 150.0 a NeubwnFlux/101 mAve Surface iHbat Fluxt&Core hn lowRa_ Core hlet Subcoig a% =4A1 --_It p a -a 125.0-0 75.0 4 2 25.0-e Dome Press Rise (psi)xSafety~alve ftwV& Relief Va ve RFaw+ Bvpass Valve Raw FHPCI Raw (% FW IN 50.0 1 oXc 0.0 10.0 Time (sec)20.0 0.0 10.0 Tine (sec)20.0 la 4~, a a 04 4, 0.0 I 0.0 10.0 20.0 0.0 10.0 20.0 rune (Sec) rum (Sec)Figure 81 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS (HBB)1 )C, QO Page 142 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I A 100.0.0 0.0 I , , ...0.0 5.0 10.0 15.0 Traw (sec)0.0 5.0 10.0 15.0 Tint (sec)1.0 0.0.o 4)~1 -1.0 a Void Reactivity

-Doppler Reactiv-Scram ReactityiI

+ Total Reactivity) ,.._, ^0.0 5.0 10.0 15.0 Time (sec)0.0 50 10.0 raw (sec)15.0 Figure 82 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS (UB))Page 143 BROWNS FERRY I R AlnnA A 0000-0043-8325-SRLR Revisinn I-200.0 150.0 A 10D.0 so.o 50.0 I -s 125.0 10 2 a 75.0 a Dome Press Rise (psi))(Safet r=lve laN Bypass Valve Faw-H-FbCFhN (% FM°- -p e ---p I 25.0 4 0.0 _-0.0-25.0 _-0.0 10.0 20.0 Tne (sec)10.0 Tmne (sec)20.0 150.0 4, 100.0:,:E'.0 0.Q U 4,1 0.0 0.0 10.0 20.0 Tme (sec)0.0 10.0 20.0 Time (sec)Figure 83 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS (UB))Page 144 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I O. I O , l l 0. 5.0 10.0 15.0 Tme (sec)0.0 5.0 10.0 15.0 Time (sec)1s.0]10 0.0 .4J 0.0 5.0 10.0 15.0 Tint (sMc)0.0 5.0 10. 15.0 Time (sec)Figure 84 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS (UB))Page 145 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 150.0 A 100.0 NeubRonFux

/10)(Ave Surbm esat FluxI& Core Inlet FlowM+ Core Ine 1uboln 125.0.Z 75.0 25.0 A ' 1A 50.0 1-o r E p --t 0.0 o-0.0-25.0 10.0 Timn (sec)20.0 0.0 10.0 20.0 lmn (sec)150.0 ,0 100.0 150.50.0.a 0 00 Q V U 0.0 10.0 Tlne (sec)20.0 0.0 10.0 20.0 rum (see)Figure 85 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS (UB))CQpLP Page 146 I:

BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision 1 20D.0 4)4 100.0 4)0.0 3.0 Time (sec)60 0.0 30 Time (sec)6.0 10100.0 4)6 0.a 2 U 4);I 0.0 3.0 6.0 0.0 3o 6,0 Rae (sec) Time (sec)Figure 86 Plant Response to Load Rejection w/o Bypass (MOC ICF with PLUOOS & RPTOOS (HBB))Page 147 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision 1 la 0.0 3.0 6.0 0.0 3.0 Tun (sec) Tom (sec)6.0 1 100.0 4J C So 00 C.(J 0.0 3.0 6.0 0.0 3.0 Time (see) Tine (sec)Figure 87 Plant Response to Load Rejection w/o Bypass (EOC ICF with PLUOOS & RPTOOS (HBB))Page 148 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I.200.0-- Dome Press Rise (psi)SaBetysVahe Fw s Rele aisFlo* Bypass Vbae Favv 100.0 0.0 1-0.0 0.0 A A _ _ r .3.0 Time (sec)6.0 0.0 1.0 4-.0.0 2 6. -.0 -o 6. m .ao-rum (sec)6.0 0 3a0 Tim (sec)3.0 TmR (sec)6.0 Figure 88 Plant Response to Load Rejection w/o Bypass (MOC MELLLA with PLUOOS & RPTOOS (HBB))c 6 Page 149 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 300.0 1-Dome Press Rise (psi)Safety Vahoe now-- RelifValveFRaw A Bypass Vahe FlRN , 200.0'I AN 100.04/~ r 0.0 I 0.0 3.0 Time (sec)-4 6'1 200.0 , 100.0 0.0-100.0 e Level(inch-REF-SEP-SKRT)

-Vessel Steam Flow-a Turbine Sleam Row_ Feedwater Row TS?^0.0 ] -0.0 1.0 a U o o.o~ 10 ao Time (sec)60 0.0 30 Time (sec)6.0 0.0 3.0 Time (sec)6.0 Figure 89 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with PLUOOS & RPTOOS (HBB))C 9A Page 150 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 100.0'N 0.0 I 0.0 3.0 Tme (see)A.U.U 9;100.0 0.1 60 0.0 U_- $ -1.0 6.0 0.0 30 6.0 Tim (sec)-100.0 1 0.0 3.0 Tim (see)3o Time (sec)6.0 Figure 90 Plant Response to Load Rejection w/o Bypass (EOC ICF with PLUOOS & RPTOOS (UB))Page 151 I:

BROWNS FERRY I RPl-. nsl 0000-0043-8325-SRLR Pa,;cian 1 rvsluau v rvvla-ul Xl a Dome Press Rise (psi)x Safety VaW Flow_ Bypass \VaSf Flo 0.0 _0.0 3.0 Tmx (Sec), 200.0 A 100.0 0.0 -6.0 0.0 1.0 a*30 0.0 --0.0 0--2.0 -02.0_ _ _3.0 Trm (sec)6.0 v10 12-.1-100.0 I 0.0 3.0-rue (sec)3.0 60 Time (sec)Figure 91 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with PLUOOS & RPTOOS (UB))Page 152 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 0.0 3.0 6.0 0.0 3.0 Time (sec) -rme (sec)6.0 1R 4., E a 0 0 4, 0.0 3.0 Tue (sec)6.0 0.0 3.0-rum (sec)6.0 Figure 92 Plant Response to Load Rejection w/o Bypass (MOC ICF & FWTR with PLUOOS & RPTOOS (HBB))cu T Page 153 BROWNS FERRY 1 Reload 6 0000-0043-8325-SRLR Revision I 200.0 150.0 we A 100.0 50.0 0.0 0.200.0 ,, 100.0 0.0-100.0 0o ao 6.0 0.0 30 Trw (sec) Tue (sec)6.0 1.0 6'a 0 0.U 19 -1.0-2.0 0O 3.0 Tune (sec)6.0 0.0 3.0 6.0 Tine (sec)Figure 93 Plant Response to Load Rejection w/o Bypass (EOC ICF & FWTR with PLUOOS & RPTOOS (HBB))C(-Z~Page 154 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 0.0 3.0 6.0 0.0 30 6.0'rue (sec) Tam (sec)200.0 100.0 a Leve (inch-REF-SEP-SKRT)

-*-Vessel Stean Flow-a Turbine Steam Raw-Feedwater Flaw A/V'I 0 t 0:P e 0.0-100.0 0.0 3.0 Tme (sec)6.0 0.0 3.0 ,rm (Sec)Figure 94 Plant Response to Load Rejection w/o Bypass (MOC MELLLA & FWTR with PLUOOS & RPTOOS (HBB))CQWT Page 155 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision 1 200.0 150.0 4)A 100.0 soic.o 50.0 0.0 0.200.0 on 100.0 0.0.0 ZW.U 4)100.0 0.0 -6.0 0.0 0 3.0 Time (sec)3.0 Rane (sec)6.0 00 a 0 4.C 04 0.0 3.0 6.0 0.0 3.0 Time (sec) 1-nne (sec)60 Figure 95 Plant Response to Load Rejection w/o Bypass (EOC MELLLA & FWTR with PLUOOS & RPTOOS (HBB))Page 156 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 0.0 L-0a0 3.0 6.0 0.0 30 6.0 rue (sec) Tine (sec)0 0 I t 8 t,'9 0.0 3.0 Tile (see)60 0.0 300 6.0 Time (see)Figure 96 Plant Response to Load Rejection w/o Bypass (EOC ICF & FWTR with PLUOOS & RPTOOS (UB))c95 Page 157 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 2Do.0 0.0 100.0 R Qo 4 W.3.0 6.0 0.0 3.0 Yme (Sec) Tm (sec)tel(inch-REF-SEP-SKRT React ssel Steam FRaw er vity trie Steam Raw 1.0 R xWater FRaN wtaR 0.0 V -1.0-2.0 3.0 6.0 0.0 3.0 Tm (sec) Tm (sec)Figure 97 Plant Response to Load Rejection w/o Bypass (EOC MELLLA & FWTR with PLUOOS & RPTOOS (UB))6.0 0.0 6.0 C CY Page 158 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 0.0 5.0 10.0 Time (sec)150.0-.75.0 A \25.0-25.0 15.0 20.0 0.0 5.0 10.0 Time (sec)RT) -Void Reactiity Doppler Reactvit 1.0 -a- Scram Reactvit l Total Readvity o3 0.0-1.0-2.0 15.0 20.0 0.0 5.0 10.0 Tmue (sec)15.0 20.0 ,a 100.0 50.0 0.0 5.0 10.0 Tune (sec)15.0 20.0 Figure 98 Plant Response to FW Controller Failure (MOC ICF with TBVOOS & RPTOOS (HBB))c9-1 Page 159 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0 I l125.0 , 75.0 4~1 4 a Dome Pass Rise (psi)xSafety Vahhe Faw Relief Vahe Flow s Bypass \khe Raw\HPCI Flow (% FVC_~ o 25.0 4-25.0 I o0c 0.0 10.0 20.0 TmR (sec)o 10.0 20.0 Tim (sec)150.0 la 100.0 50.0 0.0 1.0 a 0 3Q 0 4.'04 -1.0-2.0 0.0 10.0 20.0 Tint (sec)0.0 10.0 20.0 Tme (Sec)Figure 99 Plant Response to Inadvertent HPCI /L8 (MOC ICF with TBVOOS & RPTOOS (HRB) )ceq Page 160 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 0.O 5.0 10.0 15.0 20.0 0.0 5.0 10.0 Tme (sec) Tin (sec)15.0 20.0 150.0 ,,100.0 N.o 50.0 0.0-0.0 a 4)a o0.0 57- X 0_ I-2.0 15.0 20.0 .0 5.0 10.0 Tim (sec)5.0 10.0 Tme (sec)15.0 20.0 Figure 100 Plant Response to FW Controller Failure (EOC ICF with TBVOOS & RPTOOS (HBB))P e16 Page 161 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 0.0 10.0 20.0 0.0 10.0 200 Tume (sec) Tum (sec)10 2 19-a Level(inch-REF-SEP-KT)

Vessel Steamn Flow iso.0 -- Turbine Steam Flow+ Feedcater Flow 100.0 :am 1o.o L 50.0 0 a t 0'4 A 0.0 i I I 0.0 10.0 20.0 Tume (sec)0.0 10.0 20.0 Time (sec)Figure 101 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS & RPTOOS (HBB)1 )c / Do Page 162 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0 150.0 125.0 -75.0 10 2 ,% 100.0 09.-I a Dome Press Rise (psi)xSafety Bve Flow 6 Relief Vaye Flao_ Bypass MaKe Raw 25.0--I -25.0 -15.0 20.0 0.0 l l ,, I , .0.0 5.0 10.0 Time (sec)50 10.0 Tinm (sec)15.0 20.0 150.0 1.0 a 100.0 ZJ o 0.0 0 15 i -1 .0 50.0 0.0-2.0 0.0 5.0 10.0 Tie (sec)15.0 20.0 0.0 5.0 10.0 Tire (sec)15.0 20.0 Figure 102 Plant Response to FW Controller Failure (MOC MELLLA with TBVOOS & RPTOOS (HBB))CIO'Page 163 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0 150.0 I 100.0 50.0 I 125.0.0 75.0 a Dome Press Rise (psi)xSafety Valve Flow RelieFValve Raw-Bypass Vale Ralw a HPCI RaN (% FW)-4-- ----° °25.0-- -- 0.0 o.o 10.0 20.0 Time (sec)0.0 10.0 20.0 Time (sec)150.0 10 100.0 V-Level(inch-REF-SEP-SKRT)

Vessel Steam Fblw-& Turbine Steam Row,_ Feedwater Roaw Wil Kj >6 2 1.0 E a 0 t U Z1 04 -1.0-2.0 50.00.0 10.0 Time (see)20.0 0.0 10.0 20.0 Time (sec)Figure 103 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA with TBVOOS & RPTOOS (HBB)1 )1 o1-, Page 164 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0 150.0 1so0 4 100.0 50.0 Q0.0.0 5.0 10.0 Time (sec)15.0 20.0 0.0 5.0 10.0 Time (Sec)15.0 20.0 4.-.1 o .0._~ Total Readthit'A l 5 I4..t -1.0-2.0 15.0 20.0 0.0 5.0 10.0 Tme (aec)0.0 I-0.0 5.0 100 Tra (Sec)15.0 20.0 Figure 104 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS & RPTOOS (HBB))Page 165 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision 1 125.0*e 75.0 4.p 100.0-Dome Press Rise (psi)xSafio-t Valve Raw 6 Relief Vadve Row_ Bypas Vahe Flow+ HPCI Row (% FR p-- o o 25.0--25.0 , 0.0 10.0 20.0 Time (sec)0.0 10.0 20.0 The (sec)150.04-Level(inch-REF-SEP-SKRT)

\kVssel Steam Fbw A Turbine Steam RoN_ Feedwater Row X 100.0 50.0 a 0.W C)g o.o~ 10 t,:E 4 -1.0 s 0.0 _-0.0 10.0 Thm (Sec)20.0 0.0 10.0 Tmr (sec)20.0 Figure 105 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS & RPTOOS (HBB)1 )Pa g 0 S Page 166 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 2M0.0 0.0 5.0 10.0 15.0 20.0 0.0 5.0 10.0 Tune (Sec) Tre (sec)15.0 20.0 150.0 a C3 ca.50.0 00 0.0 5.0 10.0 Tine (sec)15.0 20.0 0.0 5.0 10.0 Time (sec)15.0 20.0 Figure 106 Plant Response to FW Controller Failure (EOC ICF with TBVOOS & RPTOOS (UB))cf5, Page 167 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 2Do.0 150.0I 1w0.A 100.0-- Neton Flux / 10-- Ave Surface Heat Flux eh Core Inlet Flow_ Core Inlet Subcooling 50.0.a a a a o u no I -p 0.0 10.0 Tmm- (see)20.0 0.0 10.0 20.0 rune (see)150.0 10 100.0 50.0 -4.a M I 0 U 0::0 0.0 100 20.0 Tnne (see)0.0 10.0 20.0 rune (see)Figure 107 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS & RPTOOS (UB))cIloc.Page 168 BROWNS FERRY 1 Reload 6 0000-0043-8325-SRLR Revision I 0.0 I 0.0 5.0 10.0 Tine (sec)150.0 50.0 00 0.0 I O5.U 25.0 I.-25.0 15.0 20.0 0.0 5.0 10.0 Tint (sec)QRT) -Void ReactMty xDopplerRec

-.0 -Scram Reactivity Fe:- Total Reacfiy e0.0 S -1.0-2.0 15.0 20.0 0.0 5.0 10.0 Timn (sec)15.0 20.0 5.0 10.0 Tint (sec)15.0 20.0 Figure 108 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS & RPTOOS (UB))COX Page 169 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision 1 125.0 +-Dome Press Rise (psi)Safety \Mkhe Flow-# RlRf#(% Flw s Bypass \kde Ra 9 WCI Fiow (% FW).5 4 100.0 50.0 0.0 C 150.0 ,$ 100.0 50.0 V. 75.0 2.0 25.0_I eo 10.0 20.0 Time (sec)-Level(inch-REF-SEP-SKRT)

  • Vessel Steam Flow Turbine Steam Flow-Feedwater Raw Y _ f ks a -- -- .--!-25.0 0.0 10.0 20.0 Time (sec)a Void Reacti vit Doppe Re ty 1.0 Suam Reacti+Tota Reactivity
0. 0 a a 0 0 C..E 4E-1.0 u.u I .- --2.u 0 4 -0.0 10.0-rme (sec)20.0 0.0 10.0 Time (sec)20.0 Figure 109 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS & RPTOOS (UB))crma Page 170 BROWNS FERRY I R 1-.A A 0000-0043-8325-SRLR RDavicroI 1 kv%.fa. U VVVI3UUIa II 150.0 A 100.0 50.0 Cal NO Of 0.0 5.0 10.0 15.0 Trme (sec)0.0 10.0 Trme (sec)15.0 we 100.0'N 1.0 14 a a-1.0 0.0 I-U0-2.0 5.0 10.0 15.0 Tme (sec)0.0 5.0 10.0 15.0 Tne (se)Figure 110 Plant Response to FW Controller Failure (MOC ICF & FWTR with TBVOOS & RPTOOS (HBB))Page 171 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0 150.0 1 a Neuro FLux /10-Ave Surface Heat Rlux-rCore Wet low-Core Wet Subcoofing IX 4)soN 0.0 4la io a a a a A p. -0.0 10.0 Time (sec)20.0 0.0 10.0 20.0 uerm (sec)150.0 10 100.0 ic.o 50.0 0.0 a S)i I 0 4.0.0 10.0 20.0 0.0 10.0 20.0 Tme (sec) Time (sec)Figure 111 Plant Response to Inadvertent HPCI /L8 (MOC ICF & FWTR with TBVOOS & RPTOOS (HBB)1 )clo Page 172 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 0.0 I i , I I , I 0.0 5.0 10.0 15.0 Ymhe (sec)0.0 5.0 10.0 15.0 Trm (sec)150.0 50.0 0.0 5.0 10.0 15.0 Time (SM)0.0 5.0 10.0 15.0 rm (sec)Figure 112 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS & RPTOOS (HBB))C I T I Page 173 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision 1 I 125.0 e0 75.0 a Dome Press Rise (psi)Safetyhe Ra 6 RI&ahe Raw s Bypass \kahe Raw~H PCI Raws (% FWV)r 25.0 4-25.0 _-0.0 0.0 10.0 20.0 Trm (sec)10.0 Time (sec)20.0 150.0 ,x 100.0 50.0:E 4I a 0.a C C)0.0 100 20.0 Tue (sec)0.0 10.0 20.0-Rmae (sec)Figure 113 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS & RPTOOS (HBB))ClIf f-z Page 174 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0 150.0 sa A 100.0 50.0 o.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 rmu (sec) Time (sec)150.0 la 100.0 50.0'4 3 a.0 a 0 S U 4)0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tint (sec)Figure 114 Plant Response to FW Controller Failure (MOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB))C113 Page 175 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I AJ.UA I ^150.0 I.5 j 100.0 50.0 0.0 9 Nettron Flux/ 10 x Ae Surface Fleat FluxI% Core Inlet RaowI_-o Core Inlet Subco olir-t A p o 1 a o o o f 125.0 --, 75.0-25.0 a Dome Press Rise (psi)) Safety ahe FlON& Relief \h31e Flow+ Bypass \klve Flow a FPCI Rlaw (% FW\)0 0 $l S O 00 10.0 Time (sec)20.0 0.0 10.0 Time (sec)20.0.5 4J 0 2 0:E Q.S 0.0 I 0.0 10.0 20.0 Tinm (sec)0.0 10.0 20.0 Time (sec)Figure 115 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB)1 )Page 176 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 0.0no 'e i , -25.0 1 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 TRme (sec) rm (sec)150.0 1, 100.0 a c 0 U tS:E Uy 0.0 5.0 10.0 15.0 Time (see)0.0 5.0 10.0 15.0 Tt (sec)Figure 116 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB))(,K Page 177 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision 1 aNeutrnFlux/10

)(Ave Surmface Iat Flux-&CorelE Ir Fo_ CoehleSubcoofirig I 15oo0 40J A\50.0 1 I o1 B: i: p p -01c I 0.0 10.0 Tom (sec)20.0 0.0 10.0 20.0 TInE (sec)la ix0.o a 1.0 a U g3 0.0 4)-1.0-2.0 0.0 10.0 20.0 Tmue (sec)0.0 10.0 20.0 Tum (sec)Figure 117 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB)1 )Page 178 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I la S 4-.1 Q0. i , 0.0 5.0 10.0 15.0 Tme (sec)0.0 50. 10.0 15.0 Tri (sec)150.0 50 10D.0 50.0 1.0I Ft2 a a C 0.0 C..a 0:g U X -1.0-2.0 a Void Reactity-Doppler Reactivity

-Scram Reactivity

_ Total Reactivity e /) a .0.0 _-0.0 I,,,, I , 1 5.0 10.0 15.0 Time (sec)0.0 5.0 iMO Time (sec)15.0 Figure 118 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS & RPTOOS (UB))c II-r Page 179 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I 200.0 150.0 la 1SO 4 100.0 50.0 0.0 0 15D.0 la 100.0 125.0.0 75.0 25.0 aDone Press Rise (psi)xSafety \hhe FlOw sReliefVav Flo*Bypass Whe Flo e FIPCI Raow (% FM\-25. o.0 10.0 20.0 Tin (sec)0.0 10.0 20.0 Tinm (sec)a Level(inch-REF-SEP-SKRT)

  • Vessel Steam Fow Turbine Stearn FlaNv-_- FeedM'ater Flow_a 1 1.I 1 1 t a Cs t 6 I.t 9X u.u ,¶- -A-0.0 00 20.0 0.0 10.0 20.0 Trnie (sec)Time (sec)Figure 119 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS & RPTOOS (UB))CT 180 Page 1 80 BROWNS FERRY I PAlnali A 0000-0043-8325-SRLR Revisinn I 200.0 4)'N 0o 5.0 10.0 15.0 Tme (sec)4)2 A 4)0.0 5.0 10.0 15.0 Tun (sec)1 .00.0 4)0.0 5.0 10.0 15.0 True (see)0.0 5.0 10.0 15.0 Tme (sec)Figure 120 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS & RPTOOS (UB))cag 1 Page 181 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision 1 200.0 150.0 V.100.0 50.0 e on Fl ux/10 x Ave Surface Fbat F Iux-Core Inlet Raw-Core Inlet Subcooling

% 1 0 3 0 0 0.?0 0.0 10.0 Time (sec)20.0 0.0 10.0 20.0 Time (sec)150.0 la 100.0 0 50.0 a 4E C).0.0 0.0 10.0 20.0 0.0 10.0 20.0'rum (sec) Time (sec)Figure 121 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS & RPTOOS (UB))c tO Page 182 BROWNS FERRY I Reloadl A 0000-0043-8325-SRLR Revisinn I-150.0 I.0.0 4.0 8o 0.0 4.0 Trm (sec) Trne (sec)8o X 100.0 01 0 0.0 4.0 8.0 0.0 4.0 Tinm (sec) Tir (sec)8o Figure 122 Plant Response to MSIV Closure (Flux Scram) -ICF (HBB)Page 183 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I---200.0 -150.0 100.0 so.o 50.0 0.0 -0.0 200.0 l 100.0 _0.0-100.0 0.0 4.0 Tune (Sec)AA.100.0-0.0 -1 8.0 0.0 1.0 0.0 0 U (:1 04 -1.0 80 0.0 4.0'rune (se)8.0 4.0 Tue (s)4.0 Time (sec)8.0 Figure 123 Plant Response to MSIV Closure (Flux Scram) -MELLLA (HBB)Cyz-z Page 184 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I Appendix A Analysis Conditions The reactor operating conditions used in the reload licensing analysis for this plant and cycle are presented in Table A-1. The pressure relief and safety valve configuration for this plant are presented in Table A-2. Additionally, the operating flexibility options listed in Section 8 are supported by the reload licensing analysis.'

4 Table A-1 Reactor Operating Conditions Analysis Value Parameter ICF LCF ICF LCF NFWT NFWT RFWT RFWT Thermal power, MWt 3952.0 3952.0 3952.0 3952.0 Core flow, Mlb/hr 107.6 101.5 107.6 101.5 Reactor pressure (core mid-plane), psia 1066.0 1064.8 1055.4 1054.3 Inlet enthalpy, Btu/lb 524.7 522.9 517.0 514.9 Non-fuel power fraction 0.036 0.036 0.036 0.036 Steam flow, Mlb/hr 16.46 16.45 15.38 15.37 Dome pressure, psig 1035.0 1035.0 1025.1 1025.1 Turbine pressure, psig 974.0 974.0 971.6 971.6 Table A-2 Pressure Relief and Safety Valve Configuration Valve Type Number of Lowest Setpoint NUvalves (psig)Safety/Relief Valve 13 1169.1 14 The number of valves shown in column 2 of Table A-2 represents the total number Safety/Relief valves configured at the plant. The reload licensing analysis assumed 12 Safety/Relief valves operable to support the SRVOOS flexibility option identified in Section 8.Page 185 BROWNS FERRY 1 0000-0043-8325-SRLR Reload 6 Revision I Appendix B Decrease in Core Coolant Temperature Events The Loss-of-Feedwater Heating event was analyzed at 100% rated power using the BWR Simulator Code. The use of this code is permitted in GESTAR II. The transient plots, neutron flux, and heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code; therefore, those items are not included in this document.

The OLMCPR result is shown in Section 11.In addition, the Inadvertent HPCI start-up event was shown to be bounded by the LFWH event in accordance with Determination of Limiting Cold Water Event, NEDC-32538P-A, February 1996. The Inadvertent HPCI with a Turbine Trip results are presented in Sections 9 and 11 and have been confirmed to be bounded by other pressurization events for Browns Ferry Unit 1 Cycle 7.Page 186 BROWNS FERRY 1 0000-0043-8325-SRLR Reload 6 Revision I Appendix C Expanded Operating Domain Analyses To provide Browns Ferry Nuclear Plant Unit 1 with operating improvements, expanded operating domain analyses were performed for maximum extended load line limit (MELLL) operation (99% flow), increased core flow (ICF) operation up to 105% of rated flow, final feedwater temperature reduction (FFWTR) and feedwater heaters out-of-service (FWHOOS) at a temperature of 339.81F (-54.7 0 F at rated power), turbine bypass valves out-of-service (TBVOOS), and recirculation pump trip out-of-service (RPTOOS).

In addition, in the event of power load unbalance failure (PLUOOS), limits have also been provided.Coastdown operation beyond full power operation to 40% power is conservatively bounded by the MCPR operating limits given in Section II of this document at the applicable core flow and feedwater temperature conditions in the expanded operating domain (Reference C-1).Maximum Extended Load Line Limit The operating domain MELLL was established for Browns Ferry Nuclear Plant Unit 1 in Reference C-2.Increased Core Flow and Final Feedwater Temperature Reduction Operation with ICF throughout the operating cycle and with ICF and FFWTR at the end of the operating cycle was justified for Browns Ferry Nuclear Plant Unit I in Reference C-3.Feedwater Heaters Out-of-Service (FWHOOS)Operation with FWHOOS (-54.7 0 F at rated power) throughout the cycle was justified for Browns Ferry Nuclear Plant Unit 1 in Reference C-3. The operating limit MCPR for FWHOOS is bounded by the operating limit for FFWTR (-54.7 0 F at rated power).Power Uprate Operation with power uprated to 3952 MWth was justified for Browns Ferry Nuclear Plant Unit I in Reference C-3.Turbine Bypass Valve Out-of-Service (TBVOOS)Operation with TBVOOS was justified for Browns Ferry Nuclear Plant Unit 1 in References C-3, C-5 and C-7.Page 187 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I EOC Recirculation Pump Trip Out-of-Service (EOC-RPTOOS)

Operation with the EOC RPTOOS was justified for Browns Ferry Nuclear Plant Unit I in Reference C-3, C-5 and C-7.Turbine Bypass and Recirculation Pump Trip Out-of-Service Operation with the combined Turbine Bypass and Recirculation Pump Trip (RPT) Out-of-Service condition was justified in Reference C-7.Rod Block Monitor (RBM) Considerations The ARTS Rod Withdrawal Error (RWE) analysis validated that the following MCPR values provide the required margin for full withdrawal of any control rod during Browns Ferry Nuclear Plant Unit I Cycle 7: For Power < 90%: MCPR 2 1.70 For Power 2 90%: MCPR 2 1.40 The reported results below are a maximum of the cycle specific and the generic limit for each setpoint.The RWE OLMCPR values for the 114% and 117% HTSPs are the same as the generic values calculated in Reference C-2 scaled by the change in the Browns Ferry Nuclear Plant Unit 1 Cycle 7 safety limit.HTSP Reference C-2 Browns Ferry 1 Cycle 7 Without RBM Filter MCPR Limnit (based on 1.07 SL) Rated MCPR Limit (based on a 1.09 SL)107% 1.20 1.32 111% 1.25 1.32 114% 1.30 1.32 117% 1.35 1.38 Filtered setpoints are specified to be lower than unfiltered setpoints due to the additional lag or delay time associated with filtering.

The RWE results shown above for the four HTSPs are unblocked for the Cycle 7 specific calculation.

Thus the results for the filtered signals would remain the same as the lags or delays in the block associated with the filtered signal makes no difference in the results.ARTS Power and Flow Dependent Limits The ARTS power and flow dependent operating limits for all operating flexibility options are provided in Reference C-6.The Reference C-6 MCPRp limits are calculated for a SLMCPR of 1.09. The Reference C-6 Kp limits are based on a PLU Power Level of 50% rated power.The Reference C-6 MCPRf limits are calculated for a SLMCPR of 1.09.The Reference C-6 LHGRFACp limits are based on a PLU Power Level of 50% rated power.Page 188 BROWNS FERRY I 0000-0043-8325-SRLR Reload 6 Revision I The Reference C-6 LHGRFACf limits remain unchanged from Reference C-2.SLO Pump Seizure Operating Limit The cycle-independent OLMCPR calculated for a recirculation pump seizure event when operating in Single Loop Operation (SLO) is 1.51. When adjusted for the off-rated power/flow conditions for SLO (i.e., Kp), this limit corresponds to a rated power/flow OLMCPR of 1.35, assuming SLO SLMCPR <1.11.To ensure that the SLO pump seizure analysis is bounded for the current operating cycle, Browns Ferry I Cycle 7, the rated OLMCPR must be set 2 1.35 when operating in SLO.

References:

C-I General Electric Standard Application for Reactor Fuel, GESTAR II, NEDC-2401 1-P-A-15, September 2005 and GESTAR II US. Supplement, NEDC-2401 I-P-A-15-US, September 2005.C-2 Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Units 1, 2 and 3, NEDC-32433P, April 1995.C-3 Browns Ferry Unit I Safety Analysis Report for Extended Power Uprate, NEDC-33101P, Revision 0, June 2004.C-4 Browns Ferry Nuclear Plant Units 1, 2 and 3 Single Loop Operation, NEDO-24236, May 1981.C-5 Safety Analysis for Browns Ferry Nuclear Plant Units 1, 2 and 3 Turbine Bypass and End-of-Cycle Recirculation Pump Trip Out-of-Service, NEDC-32774P, August 1997.C-6 Tennessee Valley Authority Browns Ferry Unit I Off-Rated and PLU OOS Analyses, GE-NE-0000-0052-1735-RO, May 2006.C-7 Safety Analysis for Browns Ferry Nuclear Plant Units 1, 2 and 3 Turbine Bypass and End-of-Cycle Recirculation Pump Trip Out-of-Service Combination Mode Out-of-Service, NEDC-32774P, Supplement 1, February 2001.Page 189 BROWNS FERRY I 0000-0043-8325-SRLR Reload 6 Revision I Appendix D Thermal Mechanical Compliance A thermal mechanical compliance check is performed for the fast pressurization transients as well as for the loss-of-feedwater heating event and rod withdrawal error to assure that the fuel can operate without violating the thermal mechanical design limits. These limits are established such that reactor operation within these limits provides assurance that the fuel will not exceed any thermal mechanical design or licensing limits during all modes of operation.

All thermal mechanical limits are met for Browns Ferry I Cycle 7.Page 190 BROWNS FERRY I Reload 6l 0000-0043-8325-SRLR Revision 1 Appendix E Variable Frequency Drives (VFD) Application To improve the reliability of the recirculation system, Browns Ferry Unit 1 has replaced the recirculation M/G (Motor/Generator) sets with Variable Frequency Drives (VFD). Operation with VFD was modeled in this reload analysis.Page 191 BROWNS FERRY 1 Relonad 6 0000-0043-8325-SRLR Reviqinn 1 Appendix F List of Acronyms Acronym Description ACPR Delta Critical Power Ratio Ak Delta k-effective 2RPT Two Recirculation Pump Trip ADS Automatic Depressurization System ADSOOS Automatic Depressurization System Out of Service AOO Anticipated Operational Occurrence APRM Average Power Range Monitor ARTS APRM, Rod Block and Technical Specification Improvement Program BOC Beginning of Cycle BSP Backup Stability Protection Btu British thermal unit BWROG Boiling Water Reactor Owners Group COLR Core Operating Limits Report CPR Critical Power Ratio DIVOM Delta CPR over Initial MCPR vs. Oscillation Magnitude DR Decay Ratio DS/RV Dual Mode Safety/Relief Valve ECCS Emergency Core Cooling System ELLLA Extended Load Line Limit Analysis EOC End of Cycle (including all planned cycle extensions)

EOR End of Rated (All Rods Out 1000/oPower

/ 100%Flow / NFWT)ER Exclusion Region FFWTR Final Feedwater Temperature Reduction FMCPR Final MCPR FOM Figure of Merit FWCF Feedwater Controller Failure FWHOOS Feedwater Heaters Out of Service FWTR Feedwater Temperature Reduction GDC General Design Criterion GESTAR General Electric Standard Application for Reactor Fuel GETAB General Electric Thermal Analysis Basis GSF General Shape Function HAL Haling Burn HBB Hard Bottom Burn HBOM Hot Bundle Oscillation Magnitude HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line HPCI High Pressure Coolant Injection ICA Interim Corrective Action Page 192 BROWNS FERRY I Reload 6 0000-0043-8325-SRLR Revision I Acronym Description ICF Increased Core Flow IMCPR Initial MCPR IVM Initial Validation Matrix Kf Off-rated flow dependent OLMCPR multiplier Kp Off-rated power dependent OLMCPR multiplier L8 Turbine Trip on high water level (Level 8)LCF Low Core Flow LHGR Linear Heat Generation Rate LHGRFACf Off-rated flow dependent LHGR multiplier LHGRFACp Off-rated power dependent LHGR multiplier LOCA Loss of Coolant Accident LPRM Local Power Range Monitor LRHBP Load Rejection with Half Bypass LRNBP Load Rejection without Bypass LTR Licensing Topical Report MAPFACf Off-rated flow dependent MAPLHGR multiplier MAPFACp Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPRf Off-rated flow dependent OLMCPR MCPRp Off-rated power dependent OLMCPR MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ MELLLA Plus MOC Middle of Cycle MRB Maximal Region Boundaries MSIV Main Steam Isolation Valve MSIVOOS Main Steam Isolation Valve Out of Service MSR Moisture Separator Reheater MSROOS Moisture Separator Reheater Out of Service MTU Metric Ton Uranium MWd Megawatt day MWd/ST Megawatt days per Standard Ton MWd/MT Megawatt days per Metric Ton MWt Megawatt Thermal NBP No Bypass NCL Natural Circulation Line NFWT Normal Feedwater Temperature NOM Nominal Burn NTR Normal Trip Reference OLMCPR Operating Limit MCPR OOS Out of Service OPRM Oscillation Power Range Monitor Pbypass Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed Pdome Peak Dome Pressure Page 193 BROWNS FERRY 1 D1-I-A A 0000-0043-8325-SRLR Rpuisinn 1 LI---]LJQU v Acronym Description PsI Peak Steam Line Pressure Pv Peak Vessel Pressure PCT Peak Clad Temperature PHE Peak Hot Excess PLHGR Peak Linear Heat Generation Rate PLU Power Load Unbalance PLUOOS Power Load Unbalance Out of Service PRFDS Pressure Regulator Failure Downscale PROOS Pressure Regulator Out of Service_/A Heat Flux RBM Rod Block Monitor RC Reference Cycle RCF Rated Core Flow RFWT Reduced Feedwater Temperature RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS Recirculation Pump Trip Out of Service RV Relief Valve RVM Reload Validation Matrix RWE Rod Withdrawal Error SC Standard Cycle SL Safety Limit SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRLR Supplemental Reload Licensing Report S/RV Safety/Relief Valve SRVOOS Safety/Relief Valve(s) Out of Service SS Steady State SSV Spring Safety Valve STU Short Tons (or Standard Tons) of Uranium TBV Turbine Bypass Valve TBVOOS Turbine Bypass Valves Out of Service TCV Turbine Control Valve TCVOOS Turbine Control Valve Out of Service TCVSC Turbine Control Valve Slow Closure TLO Two Loop Operation TRF Trip Reference Function TSIP Technical Specifications Improvement Program TSV Turbine Stop Valve TSVOOS Turbine Stop Valve Out of Service TT Turbine Trip TTHBP Turbine Trip with Half Bypass TTNBP Turbine Trip without Bypass UB Under Burn Page 194

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